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Radiolysis aspects of the aqueous self-cooled blanket concept and the problem of tritium extraction

Conference · · Fusion Technol.; (United States)
OSTI ID:5866136
In the Aqueous Self-Cooled Blanket (ASCB) concept, an aqueous /sup 6/Li solution in a metallic structure is used as a fusion reactor shielding-breeding blanket. Radiolysis effects could be very important for the design and the use of an ASCB. Although many aspects of the radiation chemistry of water and dilute aqueous solutions are now reasonably well understood, it is not possible to predict the radiochemical behaviour of the concentrated candidate ASCB solutions quantitatively. However, by means of a worst case calculation for a possible ASCB for the Next European Torus (NET) it is shown that even with an important rate of water decomposition the ASCB concept is still workable. Gas bubbles and explosive mixtures can be avoided by increasing the pressure in the neutron irradiated zone and by extracting and/or recombining the radiolytically produced hydrogen and oxygen. This could require an additional inert gas loop, which could also be used as part of the tritium extraction installation.
Research Organization:
Studiecentrum voor Kernenergie, SCK/CEN Boeretang 200, B-2400 Mol (BE); Rensselaer Polytechnic Inst., Troy, NY (USA)
OSTI ID:
5866136
Report Number(s):
CONF-880505-
Conference Information:
Journal Name: Fusion Technol.; (United States) Journal Volume: 14:2
Country of Publication:
United States
Language:
English